机构

• 金属研究所 [3]
• 宁波材料技术与工程研... [2]
• 近代物理研究所 [2]
• 力学研究所 [1]

采集方式

• OAI收割 [8]

内容类型

• 期刊论文 [8]

发表日期

• 2023 [1]
• 2021 [5]
• 2019 [1]
• 2018 [1]

学科主题

筛选

浏览/检索结果: 共8条，第1-8条 帮助 条数/页： 5101520253035404550556065707580859095100 排序方式： 请选择题名升序题名降序发表日期升序发表日期降序提交时间升序提交时间降序作者升序作者降序 Effects of Zn injection on corrosion behavior and crud deposition of FeCrAl fuel cladding under subcooled nuclear boiling condition in high-temperature pressurized water 期刊论文  OAI收割 CORROSION SCIENCE, 2023, 卷号: 211, 页码: 16 作者:  Xue, Chaochao;  Zhang, Ziyu;  Tan, Jibo;  Wu, Xinqiang;  Han, En-Hou   |  收藏  |  浏览/下载：30/0  |  提交时间：2023/05/09 FeCrAl fuel cladding  Corrosion behavior  Crud deposition  Zn injection  Subcooled nuclear boiling   Irradiation behaviors of two novel single-phase bcc-structure high-entropy alloys for accident-tolerant fuel cladding 期刊论文  OAI收割 JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY, 2021, 卷号: 84, 页码: 230-238 作者:  Zhang, Zijian;  Han, En-Hou;  Xiang, Chao   |  收藏  |  浏览/下载：49/0  |  提交时间：2021/10/15 High-entropy alloy  Accident-tolerant fuel cladding  Helium-ion irradiation  Microstructure  Irradiation hardening   In situ transmission electron microscopy study and molecular dynamics simulation of dislocation loop evolution in FeCrAl alloys under Fe+ irradiation 期刊论文  OAI收割 MATERIALS TODAY ENERGY, 2021, 卷号: 21, 页码: 12 作者:  Li, Y. P.;  Yu, M. S.;  Ran, G.   |  收藏  |  浏览/下载：48/0  |  提交时间：2021/12/08 In situ TEM observation  Loop reaction  Molecular dynamics simulation  Fuel cladding  Irradiation damage   Effects of ion irradiation on Cr, CrN, and TiAlCrN coated Zircaloy-4 for accident tolerant fuel claddings 期刊论文  OAI收割 ANNALS OF NUCLEAR ENERGY, 2021, 卷号: 156, 页码: 9 作者:  Song Ligang;  Huang Bo;  Li JH(李江华);  Ma Xianfeng;  Liu Min   |  收藏  |  浏览/下载：55/0  |  提交时间：2021/05/17 Accident tolerant fuel  Cladding coatings  Zircaloy-4  Au ion irradiation  Grain boundary   A damage-effect-involved phenomenological crystal plasticity model and computational methods for mechanical responses of FeCrAl alloys 期刊论文  OAI收割 MATERIALS TODAY COMMUNICATIONS, 2021, 卷号: 28 作者:  Zhang, Jingyu;  Ding, Shurong;  Du, Shiyu   |  收藏  |  浏览/下载：26/0  |  提交时间：2021/12/01 NEUTRON-IRRADIATED MODEL  TOLERANT FUEL SYSTEM  ORIENTATION DEPENDENCE  ANISOTROPIC DAMAGE  CLADDING MATERIALS  STAINLESS-STEEL  BCC IRON  DEFORMATION  BEHAVIOR  MICROSTRUCTURE   A damage-effect-involved phenomenological crystal plasticity model and computational methods for mechanical responses of FeCrAl alloys 期刊论文  OAI收割 MATERIALS TODAY COMMUNICATIONS, 2021, 卷号: 28 作者:  Zhang, Jingyu;  Ding, Shurong;  Du, Shiyu   |  收藏  |  浏览/下载：32/0  |  提交时间：2021/12/01 NEUTRON-IRRADIATED MODEL  TOLERANT FUEL SYSTEM  ORIENTATION DEPENDENCE  ANISOTROPIC DAMAGE  CLADDING MATERIALS  STAINLESS-STEEL  BCC IRON  DEFORMATION  BEHAVIOR  MICROSTRUCTURE   Effect of aluminum content on dislocation loops in model FeCrAl alloys 期刊论文  OAI收割 NUCLEAR MATERIALS AND ENERGY, 2019, 卷号: 21, 页码: 7 作者:  Zhou, Xiong;  Guo, Liping;  Wei, Yaxia;  Wang, Hui;  Chen, Cheng   |  收藏  |  浏览/下载：30/0  |  提交时间：2021/02/02 FeCrAl alloy  Dislocation loops  Radiation damage  Accident tolerant fuel cladding   Microstructural evolution of epitaxial Ti3AlC2 film on sapphire under ion irradiation and nanoindentation-induced deformation 期刊论文  OAI收割 JOURNAL OF NUCLEAR MATERIALS, 2018, 卷号: 509, 页码: 181-187 作者:  Huang, Qing;  Wang, Ji;  Shao, Tao;  Ren, Donglou;  Liu, Shaoshuai   |  收藏  |  浏览/下载：52/0  |  提交时间：2018/10/08 Ion irradiation  Accident tolerant fuels  Fuel cladding coating  Ti3AlC2  MAX phase film